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Study mapping U-10Zr porosity informs metallic fuel design
Researchers at Idaho National Laboratory and the Massachusetts Institute of Technology have conducted a three-dimensional study of irradiated U-10Zr—uranium alloyed with 10 percent zirconium—across key radial regions, providing new insights into how the material swells, transfers heat, and interacts with the fuel cladding.
U-10Zr was extensively tested in historical sodium-cooled fast reactors and is now attracting attention for use in next-generation advanced reactors.
A. V. Golubeva, N. P. Bobyr, D. I. Cherkez, A. V. Spitsyn
Fusion Science and Technology | Volume 79 | Number 4 | May 2023 | Pages 488-501
Technical Paper | doi.org/10.1080/15361055.2023.2168447
Articles are hosted by Taylor and Francis Online.
In the National Research Center “Kurchatov Institute,” a complex of laboratory facilities was created for studying experimentally the interaction of hydrogen isotopes with materials. The complex includes equipment for sample preparation, facilities for plasma irradiation using distributed electron cyclotron resonance and helicon discharges, facilities for plasma-driven and gas-driven permeation measurements, a setup for thermal desorption analysis, and a multipurpose laboratory facility for solving a variety of short-term tasks. The teams of each experimental facility include students. Students of the third and fourth years from several technical universities come to the laboratory complex as interns. Depending on their personal abilities and preferences, the students are involved in different engineering, experimental, and theoretical tasks. After getting master’s degrees, the most motivated and gifted students continue their education as PhD students and work in experimental teams.